GB1321646A - Process for surface treatment of zirconium-containing cladding materials for fuel elements or other components for nuclear reactors - Google Patents
Process for surface treatment of zirconium-containing cladding materials for fuel elements or other components for nuclear reactorsInfo
- Publication number
- GB1321646A GB1321646A GB3238570A GB3238570A GB1321646A GB 1321646 A GB1321646 A GB 1321646A GB 3238570 A GB3238570 A GB 3238570A GB 3238570 A GB3238570 A GB 3238570A GB 1321646 A GB1321646 A GB 1321646A
- Authority
- GB
- United Kingdom
- Prior art keywords
- anodic oxidation
- fluoride
- fuel elements
- components
- nuclear reactors
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
- C25D—PROCESSES FOR THE ELECTROLYTIC OR ELECTROPHORETIC PRODUCTION OF COATINGS; ELECTROFORMING; APPARATUS THEREFOR
- C25D11/00—Electrolytic coating by surface reaction, i.e. forming conversion layers
- C25D11/02—Anodisation
- C25D11/26—Anodisation of refractory metals or alloys based thereon
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Chemical Kinetics & Catalysis (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Electrochemistry (AREA)
- Materials Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Chemical Treatment Of Metals (AREA)
- Cleaning And De-Greasing Of Metallic Materials By Chemical Methods (AREA)
- Treatment Of Steel In Its Molten State (AREA)
- Heat Treatment Of Articles (AREA)
Abstract
1321646 Anodizing zirconium alloy cladding INSTITUTT FOR ATOMENERGI 3 July 1970 [5 July 1969 24 Dec 1969] 32385/70 Headings C7A and C7B] Zr-base cladding material for fuel elements e.g. of VO 2 or other components for nuclear reactors is surface-treated by pickling in an aqueous fluoride-containing bath, e.g. an aqueous solution of HNO 3 and HF or NH 4 F removing or rendering harmless fluoride-containing contaminants remaining on the surface of the material by anodic oxidation, and oxidizing to apply a protective coating, e.g. by treatment with water or steam under 100 atmosphere pressure and at 400‹ C., by heating in O 2 gas or by anodic oxidation. The removal or rendering harmless of fluoride-containing contaminants and the oxidation to apply a protective coating, by anodic oxidation, may be effected in one step, e.g. in an agitated bath containing a 0À01-0À5 molar solution of alkaline electrolyte, preferably 0À1-2À0 weight per cent KoH in water, at a voltage increasing at a rate not more than 10VS to a final voltage at least 30V which is maintained until the current is constant. The anode connector metal may be the same as the anode (Zr) and the cathode may be of Pt group metal or alloy. Anodic oxidation of Zr may be effected in an electrolyte containing 0À5-3% of HNO 3 , HCl, H 2 SO 4 , H 3 PO 4 , formic or acetic acid, Na NO 3 , K 2 Cr 2 O 7 , H 2 CrO 4 , citric or tartaric acid, NH 4 -tartrate or citrate Œ NH 3 , NH 4 OH, LiOH, NaOH, KOH, EDTA + NH 3 , NaNO 2 , NaB 4 O 7 , K 2 CO 3 , Ca (OH) 2 , Ba (OH) 2 , Na 2 HPO 4 , Na 3 PO 4 , K 2 SO 3 , K 2 SO 4 , or Na 2 SO 4 . Zr base alloys are specified containing: (a) 1À52-1À54% Sn, 0À13-0À20% Fe, 0À09% Cr, 0À006-0À05% Ni, (b) 1À0% Cr, 0À16% Fe; (c) 2À5% Nb, 0À5% Ta; (d) 0À7% V, 0À75% Fe; (e) 1À2% Cu, 0À3% Fe; and (f) 0À2% Sn, 0À09% Fe, 0À07% Ni, 0À14% Nb.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
NO282169A NO122049B (en) | 1969-07-05 | 1969-07-05 | |
NO512569A NO123007B (en) | 1969-12-24 | 1969-12-24 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1321646A true GB1321646A (en) | 1973-06-27 |
Family
ID=26647475
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3238570A Expired GB1321646A (en) | 1969-07-05 | 1970-07-03 | Process for surface treatment of zirconium-containing cladding materials for fuel elements or other components for nuclear reactors |
Country Status (4)
Country | Link |
---|---|
DE (1) | DE2034863C3 (en) |
FR (1) | FR2054616B1 (en) |
GB (1) | GB1321646A (en) |
SE (1) | SE363186B (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113463161A (en) * | 2021-07-27 | 2021-10-01 | 燕山大学 | Anodic oxidation treatment method for zirconium and zirconium alloy surface |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CA944716A (en) * | 1971-02-03 | 1974-04-02 | Stuart D. Bresnick | Method for reducing hydrogen absorption of zirconium by anodizing |
DE69125249T2 (en) † | 1990-11-28 | 1997-06-26 | Hitachi Ltd | Part made of zirconium alloy with low radiation growth, its manufacturing process, fuel channel box and structure as well as their use |
US5264109A (en) * | 1991-09-16 | 1993-11-23 | Siemens Power Corporation | Zirconium and zirconium alloy passivation process |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1496994C3 (en) * | 1965-02-16 | 1975-10-30 | Siemens Ag, 1000 Berlin Und 8000 Muenchen | Process for the anodic oxidation of nuclear reactor components made of zirconium |
-
1970
- 1970-07-03 GB GB3238570A patent/GB1321646A/en not_active Expired
- 1970-07-06 DE DE2034863A patent/DE2034863C3/en not_active Expired
- 1970-07-06 FR FR7024945A patent/FR2054616B1/fr not_active Expired
- 1970-07-06 SE SE09371/70A patent/SE363186B/xx unknown
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113463161A (en) * | 2021-07-27 | 2021-10-01 | 燕山大学 | Anodic oxidation treatment method for zirconium and zirconium alloy surface |
Also Published As
Publication number | Publication date |
---|---|
SE363186B (en) | 1974-01-07 |
FR2054616B1 (en) | 1973-12-07 |
FR2054616A1 (en) | 1971-04-23 |
DE2034863B2 (en) | 1979-06-07 |
DE2034863A1 (en) | 1971-01-21 |
DE2034863C3 (en) | 1980-02-07 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |